Study on corrosion control in reactors using Radiation Induced Surface Activation (RISA) - Mechanism behind stainless steel durability due to RISA against crevice corrosion

Shogo Mabuchi*, Tatsuya Hazuku, Shin Ichi Motoda, Tomoji Takamasa, Susumu Uematsu, Masahiro Furuya

*この研究の対応する著者

研究成果: Conference contribution

抄録

This study examines a corrosion control technique for corrosion-resistant materials or of stainless steel in piping for nuclear reactors. This employs an effect of Radiation Induced Surface Activation (RISA). The experimental results revealed: (1) The mechanism behind the corrosion control proposed by the previous report was confirmed to be appropriate. This via tests that measured the amount of dissolved oxygen and iron ions, in the solution. (2) The corrosion control technique was confirmed to be useful for stainless steel with any kind of metal oxide film coating on the surface. (3) It was also shown to be useful even in actual seawater, due to biological effects, which is a far more severe environment for corrosion control than simple salt water. The corrosion control technique for corrosion-resistant material using RISA in seawater has therefore been shown to offer a significant potential for practical applications in naval architecture and marine structures.

本文言語English
ホスト出版物のタイトル18th International Conference on Nuclear Engineering, ICONE18
DOI
出版ステータスPublished - 2010
外部発表はい
イベント18th International Conference on Nuclear Engineering, ICONE18 - Xi'an, China
継続期間: 2010 5月 172010 5月 21

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
2

Conference

Conference18th International Conference on Nuclear Engineering, ICONE18
国/地域China
CityXi'an
Period10/5/1710/5/21

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

フィンガープリント

「Study on corrosion control in reactors using Radiation Induced Surface Activation (RISA) - Mechanism behind stainless steel durability due to RISA against crevice corrosion」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル